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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
D.G. Bellamy (1-416-207-6378), J.R. Robins (1-416-207-6083), K.B. Woodall (1-416-207-6835), S.K. Sood (1-416-592-5501), P. Gierszewski (1-905-823-4717)
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 525-529
Tritium Processing | Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30456
Articles are hosted by Taylor and Francis Online.
A new experimental system has been constructed to test ITER relevant distillation columns and related cryogenic distillation (CD) hardware and control systems. These columns are used to purify tritium in the ITER fuel cycle. The ITER test column reported here has a diameter of about 30 mm and a packed length of approximately 150 cm. It can operate with a hydrogen isotope (Q2) boilup of about 60 watts. Two 30 W refrigeration systems were coupled together to deliver as close as possible to 60 watts of cooling. The separation performance of the column was determined by accurately measuring the tritium concentration in the feed and product streams using a mixture of D2 and DT gas. Conditions which yield a column theoretical plate height as low as 2.05 cm. and a plate inventory of 0.118 moles are reported. The goal of this research program is to measure the performance of ITER relevant columns, packings, condensers, and reboilers in order to minimize hydrogen (Q2) and tritium holdup and to show that ITER objectives can be met with smaller diameter and lower tritium inventory columns than have previously been considered.